NL-10-0389, Cycle 15 Core Operating Limits Report

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Cycle 15 Core Operating Limits Report
ML100770079
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/17/2010
From: Stinson L
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-10-0389
Download: ML100770079 (14)
v • d • e


Text

L M. Stinson (Mike) Southern Nuclear Vice President Operating Company. Inc.

Fleet Operations Support 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 SOUTHERN'\'

March 17,2010 COMPANY Energy to Serve Your World'"

Docket No.: 50-425 NL-10-0389 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Unit 2 Cycle 15 Core Operating Limits Report Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) for Vogtle Electric Generating Plant Unit 2 Cycle 15, Version 1.

This letter contains no NRC commitments. If there are any questions, please advise.

Respectfully submitted, L. M. Stinson Vice President Fleet Operations Support MJAlPAH/phr

Enclosure:

Core Operating Limits Report, VEGP Unit 2 Cycle 15, Version 1

U. S. Nuclear Regulatory Commission NL-10-0389 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President - Vogtle Ms. P. M. Marino, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Vogtle Mr. M. Cain, Senior Resident Inspector - Vogtle State of Georgia Mr. C. Clark, Commissioner-Department of Natural Resources

Vogtle Electric Generating Plant Unit 2 Cycle 15 Core Operating Limits Report Enclosure Core Operating Limits Report, VEGP Unit 2 Cycle 15, Version 1

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 2 Cycle 15 has becn preparcd in accordance with the requirements of Technical Specification 5.6.5.

The Teehnieal Requirement affeeted by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES I and 2 The Technical Specifieations affeetcd by this report are listed below:

3.1.1 SHUTDOWN MARGIN - MODES 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Hcat Flux Hot Channel Factor - FQ(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor - FN AH 3.2.3 Axial Flux Difference 3.9.1 Boron Coneentration Page 1 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listcd in Section 1.0 are presented in the follow ing subscctions. These limits have bcen developed using NRC-approved methodologies including those specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES 1 and 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent L1k/k.

2.2 SHUTDOWN MARGIN - MODES 3, 4 and 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLIARO/HZP-MTC shall be less positive than +0.7 x 10-4 L1k/kfOF for power levels up to 70% RTP with a linear ramp to 0 L1k/k/oF at 100% RTP.

The EOLIARO/RTP-MTC shall be less negative than -5.50 x 10-4 L1k/k/ 0 F.!

2.3.2 The MTC Surveillance limits are:

The 300 ppm!ARO/RTP-MTC should be less negative than or equal to

-4.75 x 10-4 L1kJk/0 F. 1 The 60 ppm!ARO/RTP-MTC should be less negative than -5.35 x 10-4 L1k/k/°F. 1 where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 1 Applicable for full-power T-average of 584.4 to 587.4°F.

Page 2 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.

2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 3.

2.6 Heat Flux Hot Channel Factor FQ(Z) (Specification 3.2.1)

F RTP 2.6.1 FQ(Z)~+'K(Z) forP> 0.5 F RTP F Q(Z) ~ ~.5 . K(Z) for P ~ 0.5 THERMAL POWER where:

P = RATED THERMAL POWER 2.6.2 2.6.3 K(Z) is provided in Figure 4.

F RTP .K(Z) 2.6.4 FQ(Z)~ ~. W(Z) forP> 0.5 FQ RTP . K(Z)

F Q(Z) ~ 0.5. W(Z) for P ~ 0.5 2.6.5 W(Z) values are provided in Table 2.

2.6.6 The FQ(Z) penalty factors are provided in Table I.

Page 3 of 11

CORE OPERA TlNG LlMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 2.7 Nuclear Enthalpy Rise Hot Channel Factor FN t,H (Specification 3.2.2)

N RTP 2.7.1 F 5,F *(l+PFt,Jf*(l-P>>

M-I M-I THERMAL POWER where: P RATED THERMAL POWER RTP 2.7.2 F 1.65 M-I 2.7.3 PFM / = 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Acceptable Operation Limits are provided in Figure 5.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 1815 ppm. I

'This concentration bounds the condition of kcff '5 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B IO depletion.

Page 4 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 Table 1 FQ(Z) PENALTY FACTOR Cycle FO(Z)

Burnup Penalty (MWD/MTU) Factor 30 1.034 150 1.034 367 1.037 584 1.038 801 1.038 1018 1.037 1235 1.032 1453 1.026 1670 1.020 Notes:

1. The Penalty Factor, to be applied to FO(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ(Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% ofthe surveillance interval per SR 3.0.2) start ing from the burnup at which the FQ(Z) was determined.
2. Linear interpolation is adequate for intermediate cycle burnups.
3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 5 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 Table 2 RAoe W(Z)

Axial Elcvation 150 4000 12000 20000 Point (fcct) MWD/MTU MWD/MTU MWD/MTU MWD/MTU

  • I 12.00 1.0000 1.0000 1.0000 1.0000
  • 2 11.80 1.0000 1.0000 1.0000 1.0000

'" 3 11.60 1.0000 1.0000 1.0000 1.0000

'" 4 11.40 1.0000 1.0000 1.0000 1.0000

  • 5 11.20 1.0000 1.0000 1.0000 1.0000 6 11.00 1.2769 1.4370 1.3245 1.2218 7 10.80 1.2766 1.4234 1.3127 1.2126 8 10.60 1.2697 1.4064 1.3004 1.2072 9 10.40 1.2573 1.3836 1.2873 1.2016 10 10.20 1.2415 1.3588 1.2713 1.1958 11 10.00 1.2223 1.3315 1.2522 1.1948 12 9.80 1.2125 1.2997 1.2409 1.1955 13 9.60 1.2091 1.2741 1.2369 1.2004 14 9.40 1.2037 1.2574 1.2323 1.2092 15 9.20 1.1963 1.2392 1.2232 1.2172 16 9.00 1.1907 1.2212 1.2154 1.2223 17 8.80 1.1910 1.2098 1.2079 1.2259 18 8.60 1.1953 1.2074 1.2071 1.2352 19 8.40 1.2039 1.2076 1.2125 1.2499 20 8.20 1.2093 1.2056 1.2148 1.2612 21 8.00 1.2169 1.2071 1.2206 1.2742 22 7.80 1.2228 1.2074 1.2251 1.2852 23 7.60 1.2251 1.2045 1.2261 1.2921 24 7.40 1.2250 1.1996 1.2249 1.2960 25 7.20 1.2225 1.1927 1.2213 1.2968 26 7.00 1.2178 1.1841 1.2155 1.2945 27 6.80 1.2111 1.1738 1.2078 1.2894 28 6.60 1.2031 1.1626 1.198 I 1.2817 29 6.40 1.1947 1.1519 1.1874 1.2717 30 6.20 1.1857 1.1426 l.I768 1.2608 31 6.00 1.1749 1.1357 1.1640 1.2478 32 5.80 1.1655 1.1272 1.1552 1.2372 33 5.60 1.1583 1.1241 1.1559 1.2319 34 5.40 1.1557 1.1324 1.1632 1.2317 35 5.20 1.1632 1.1405 1.1686 1.2354 36 5.00 1.1706 1.1478 1.1728 1.2379 37 4.80 1.1762 1.1546 1.1759 1.2382 38 4.60 1.1812 1.1604 1.1777 1.2365 39 4.40 1.1850 1.1655 1.1783 1.2326 40 4.20 1.1878 1.1696 1.1776 1.2267 41 4.00 1.1894 1.1727 1.1754 1.2188 42 3.80 1.1899 1.1749 1.1736 1.2090 43 3.60 1.1895 1.1760 1.1733 1.1978 44 3.40 1.1893 1.1764 1.1734 1.1852 45 3.20 1.1929 1.1778 1.1725 Ll720 46 3.00 1.1989 1.1888 1.1711 1.1733 47 2.80 1.2126 1.2071 Ll745 1.1841 48 2.60 1.2331 1.2278 1.1872 1.1949 49 2.40 1.2518 1.2500 1.1979 1.2054 50 2.20 1.2704 1.2722 1.2086 1.2157 51 2.00 1.2888 1.2940 1.2192 1.2260 52 1.80 1.3066 1.3155 1.2297 1.2364 53 1.60 1.3241 1.3363 1.2401 1.2471 54 1.40 1.3408 1.3561 1.2501 1.2579 55 1.20 1.3568 1.3746 1.2598 1.2687 56 1.00 1.3713 1.3910 1.2685 1.2789
  • 57 0.80 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

'*" 59 60 0040 0.20 1.0000 1.0000 1.0000 1.0000 1.0000

  • 61 0.00 1.0000 1.0000 1.0000 1.0000

These W(Z) values are consistent with Figure 5, and are valid over the HFP Tavg temperature range from 584,4 to 587,4°F.

Page 6 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 FIGURE I REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING) 5.0 I  !

I

[ I I i r--~-

I I I 4.0 I I i i I

ACCEPTABLE OPERATING REGION I I i

~

~ (2 00 ' J.10)

~

<l 3.0 I I /

tN' I

I VV tzi REQUIRED SHUTDOWN MARGIN I ,/" V H

t!l i I i

I V

~

~ i I

(1,00 .25) vV'

§ 0 2.0 i

//

Q I /

m

~I I

til

.... I

/' I I IUNACCEPTABLE OPERATING REGION I I

(~5C, .., 0) i 1.0 I I I I

I I 0.0 I I i I I I o 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 7 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0  !

i

/

~

(2 001, .9

/

/'

V 4.0 L V

I IACCEPTABLE OPERATING REGION I /

VI'

/

....... //

..Ii!

..Ii!

<l d(>

3.0

  • 1/V
z; IREQUIRED SHUTDOWN MARGIN;; V (1 50, .8 ~)

H

(!)

~

~ /

~A 2.0

/

/

~

til /

/ UNACCEPTABLE OPERATING REGION 1.0

//  !

(~60, *a0) 0.0  ! I o 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 8 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)

~120tttttt!!!1jjjj=t~rttt~~~~tttttt H

E'i H

I'll

~ 100H-+-+-+-+-+-++-+-+--t-,

~

r:I 80

~

608+/-1tEmmEImmmmmmm~mmmm 10 20 30 40 50 60 70 POWER (% of Rated Thermal Power) 80 90 1 0

  • Fully withdrawn shall be the condition where control rods are at a position within the interval ~225 and ~ 231 steps withdrawn.

NOTE: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 115 steps.

Page 9 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2

~

1. 0

~ -

~

tl. 0.8 FQ = 2.50

~

1:-1 CORE H HT. K(Z)

..:I - - .

i00.6 0.00 1. 00 I 6.00 1. 00 I

Z 12.0 .925 1:-1

~

0.4 0.2

  • 0.0 o 2 4 6 8 10 12 CORE HEIGHT (feet)

Page 10 of 11

CORE OPERATING LlMITS REPORT, VEGP UNIT 2 CYCLE 15 FEBRUARY 2010 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FORRAOC 120 I llO R

( IS, 100) -[ (+10, 100)

U I

100

/ \ ......... ..... f - - ..-:

~

Ql 90 U ~AC 'Epr ABI E

/ \ UN CCl PTJ BLE

~

0

!l. L \ ...

r-t 1\1 80 I ~

e Ql

_.._._. ..........* / i \

.l:l Eo! 70 I

/ ArCE TA LE

\

"(j \

Ql J.J

~

1\1 60 /  !

\

0

/ \

'*' 50 V ~

~

I (-30, 50) I I (+26, 50 ) I I'z1 I

~

!l.

40 30 20 10 a

-50 -40 30 20 10 o 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent AI)

Page 11 of 11

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